Letter Sequence Request |
---|
|
|
MONTHYEARML12073A3542012-03-0909 March 2012 30-Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model Project stage: Request ML12300A2012012-10-26026 October 2012 NRC Request for Additional Information on Errors Reported Per 10 CFR 50.46, ME9119 Project stage: RAI ML12348A0552012-12-0707 December 2012 Response to RAI Regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis Project stage: Request ML13060A4172013-03-0101 March 2013 NRC Request for Additional Information on Errors Reported Per 10 CFR 50.46 (TACs ME9119, ME9120, ME9121) Project stage: RAI ML13102A0332013-04-0404 April 2013 Response to NRC RAI Regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis Project stage: Request ML13237A0022013-08-23023 August 2013 NRR E-mail Capture - Oconee Nuclear Station, Units 1, 2, and 3, NRC Request for Additional Information on Errors Reported Per 10 CFR 50.46 (TACs ME9119, ME9120, ME9121) Project stage: RAI ML13309A4462013-09-12012 September 2013 E-mail from R.Guzman to T.Byrne Request for Additional Information on Errors Reported Per 10 CFR 50.46 (TACs ME9119, ME9120, ME9121) Project stage: RAI RA-13-1002, Response to Supplemental NRC RAI Regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident2013-10-10010 October 2013 Response to Supplemental NRC RAI Regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Project stage: Request ML13338A3452013-12-0505 December 2013 Closure Evaluation for Report Concerning Significant Emergency Core Cooling System Evaluation Model Errors/Changes Project stage: Other 2013-12-05
[Table View] |
|
---|
Category:Letter
MONTHYEARML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) IR 05000269/20243012024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect ML23075A0732023-04-0505 April 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002) ML23045A1332023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter ML23045A1402023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter ML23045A1432023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23069A1102023-03-10010 March 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML23061A1772023-03-0303 March 2023 Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 ML22363A3942023-01-12012 January 2023 Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22329A1042022-11-29029 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report ML22321A1582022-11-22022 November 2022 Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 ML22301A0112022-11-0303 November 2022 Request for Withholding Information from Public Disclosure Regarding the SLR Application - September 2, 2022 ML22298A0752022-10-27027 October 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application Duke Energy Letter Dated July 25, 2022 ML22264A0322022-10-20020 October 2022 _Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Duke Energy Letter Dated July 8, 2022 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22222A0072022-09-14014 September 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application ML22231B1362022-09-0101 September 2022 Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi ML22234A0062022-08-30030 August 2022 SLRA - Closed Public Meeting Summary - August 18, 2022 2024-02-01
[Table view] |
Text
Duke 10 CFR 50.46 GARRYD. MILLER Energy Sr Vice President Nuclear Engineering Duke Energy ECO7H/ 526 South Church Street Charlotte, NC 28201-1006 Mailing Address: P.O. Box 1006- ECO7H Charlotte, NC 28201-1006 December 7, 2012 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Duke Energy Carolinas, LLC (Duke Energy)Oconee Nuclear Station, Units 1, 2, and 3 Docket Numbers 50-269, 50-270, and 50-287 Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis
Reference:
- 1) Letter, D. C. Culp (Duke Energy) to USNRC,
Subject:
Oconee Nuclear Station Day Report Pursuant to 10 CFR 50.46, Changes to or Errors in an Evaluation Model, March 9, 2012. [ADAMS Accession No. ML12073A354]
- 2) Email correspondence, John Boska (NRC) to Kent R. Alter (Duke Energy),
Subject:
Oconee Units 1, 2, and 3, NRC Request for Additional Information on Errors Reported per 10 CFR 50.46, ME9119, October 26, 2012. [ADAMS Accession No.ML12300A201]
- 3) Letter, Pedro Salas, Director, Regulatory Affairs (AREVA NP Inc.) to USNRC,
Subject:
"Generic RAI Response to a 30-day 10 CFR 50.46 Report of Significant PCT Change", (NRC:12:062), December 6, 2012.On March 9, 2012, (Reference
- 1) Duke Energy submitted a 30-day report pursuant to 10 CFR 50.46(a)(3)(ii) regarding the impact on Peak Cladding Temperature (PCT) from two errors in the Emergency Core Cooling System (ECCS) evaluation model used to assess a postulated Large Break Loss of Coolant Accident (LBLOCA) for Oconee Nuclear Station. This information is specific to the application of the AREVA ECCS evaluation model for B&W plants, as applied to Oconee Nuclear Station.The NRC transmitted, via email, (Reference
- 2) Requests for Additional Information (RAIs) regarding the Reference 1 letter, dated March 9, 2012 [ADAMS Accession No.ML12073A354]
concerning the 30-day report pursuant to 10 CFR 50.46(a)(3)(ii).
The purpose of this letter is to provide a response to the RAIs.
U.S. Nuclear Regulatory Commission December 7, 2012 Page 2 In response to the first RAI question, AREVA has submitted a generic response to the NRC in Reference
- 3. Duke Energy Carolinas has provided a response to the second RAI question, as provided in the enclosure to this letter.There are no regulatory commitments contained in this letter.Please address any comments or questions regarding this matter to Paul Guill at (704) 382-4753 (pauL guill@duke-energy.
com).Sincerely, Garry .Miller Senior Vice President Nuclear Engineering
Enclosure:
Response to NRC RAI regarding 10 CFR 50.46 Notification of Change in Peak Cladding Temperature for Large Break Loss of Coolant Accident Analysis U.S. Nuclear Regulatory Commission December 7, 2012 Page 3 xc (with attachment):
V. M. McCree, Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 J. P. Boska, Senior Project Manager (ONS)U. S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-8 C2 Rockville, MD 20852-2738 NRC Senior Resident Inspector Oconee Nuclear Station DUKE ENERGY CAROLINAS, LLC OCONEE NUCLEAR STATION, UNITS 1, 2, AND 3 ENCLOSURE RESPONSE TO NRC RAI REGARDING 10 CFR 50.46 NOTIFICATION OF CHANGE IN PEAK CLADDING TEMPERATURE FOR LARGE BREAK LOSS OF COOLANT ACCIDENT ANALYSIS 2 total pages to follow Response to NRC Requests for Additional Information (Question 1)NRC RAI Question 1 There are two changes to peak cladding temperature (PCT) for Large Break Loss of Coolant Accident (LBLOCA) analysis discussed in the report submitted by the licensee.
The first change is an Evaluation Model (EM) application error in the determination of the end of Emergency Core Cooling System (ECCS) bypass which resulted in an 80*F decrease in PCT. The second change is an EM modeling change to include the effects of the upper plenum column weldments which resulted in an 80°F increase in PCT.Provide the analysis that lead to each change having an 80 degree change in PCT.Duke Energy Carolinas Response to NRC RAI Question 1 In response to the first RAI question, AREVA has submitted a generic response to the NRC.Please see AREVA Letter from Pedro Salas, Director, Regulatory Affairs to NRC dated December 6, 2012, which transmits AREVA Document ANP-3180 (NP), Revision 0, "177 Fuel-Assembly Plant RAI Response to a 30-Day 50.46 Report of Significant PCT Change", December 2012. The AREVA report has been reviewed by Duke Energy and is provided in response to RAI Question 1 for Oconee Nuclear Station.Page 1 of 2 Response to NRC Requests for Additional Information (Question 2)NRC RAI Question 2 10 CFR 50.46(a)(3)(ii) states: " ... If the change or error is significant, the applicant or licensee shall provide this report within 30 days and include with the report a proposed schedule for providing a reanalysis or taking other action as may be needed to show compliance with 50.46 requirements...
" The PCT for LBLOCA for Oconee Units 1, 2, and 3 has changed by an absolute value of 160°F since the analysis was performed.
Simply reporting the changes and errors in the methodology does not satisfy the intent of the regulation.
Justify not providing a schedule for reanalysis or taking other action to show compliance with Section 50.46.Duke Energy Carolinas Response to NRC RAI Question 2 The response to RAI Question 1 provides additional detail regarding the analytical bases for the two peak cladding temperature (PCT) error estimates, which were based upon explicit RELAP5/Mod2-B&W code runs for the nuclear steam supply systems (NSSS) designed by Babcock & Wilcox (B&W). One error that was corrected in the evaluation models was specific to the determination of the end of emergency core cooling system (ECCS) bypass time. A separate error correction to the ECCS evaluation model was made based on the effects of the upper plenum column weldments.
As evidenced by the information provided in the response to RAI Question 1, both of these error corrections have been analyzed in detail. Furthermore, the error corrections in the ECCS evaluation model do not result in any challenge to the 10 CFR 50.46(b) acceptance criteria.
As the individual error corrections have been identified for the applicable evaluation model, and there are no other known changes identified at this time, the overall evaluation model is considered bounding and complete.The corrected ECCS evaluation model, as discussed in AREVA Report ANP-3180 (NP), will be used for any future analyses.In summary, the response to RAI Question 1 establishes the following: " The error-adjusted LBLOCA PCTs for Oconee Nuclear Station Units 1, 2, and 3 remain considerably below the 10 CFR 50.46(b) acceptance criteria." The SBLOCA analyses are not affected by the ECCS evaluation model errors.* The response provides additional information regarding the nature of the PCT error evaluations, which are supported by explicit analyses using the B&W plant ECCS evaluation model." The analysis, with the identified corrections, is considered adequate to demonstrate compliance with the requirements of 10 CFR 50.46.Based on the above, there are no adverse impacts to safety. Therefore, further LBLOCA reanalysis for Oconee Nuclear Station Units 1, 2, and 3 is not warranted.
Page 2 of 2